Published December 2005
| Version v1
Journal article
Partial service life assessment of a reactor containment
Creators
- 1. Czech Technical University in Prague, Faculty of Civil Engineering, Thakurova 7, 166 29 Prague (Czech Republic)
Description
A service life assessment of a prestressed concrete containment is developed. Liner strain is the sole limit state criterion considered, the LOCA accidents represent the load effects and the creep induced loss of prestress affects the time dependent structure resistance. Poisson, Gaussian and Ferry Borges-Castanheta processes are adopted for load models and their predictions are compared on the background of a specific PWR installation. Available experimental data is used to optimize the theoretical creep law. The Poisson and FBC processes show negligible difference for actual pulse intensities and the required service life
Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2005.06.010;
- PII
- S0029-5493(05)00236-0;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 235
- Journal Issue
- 23
- Journal Page Range
- p. 2451-2462
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37062286
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CONTAINMENT; CREEP; LOSS OF COOLANT; PRESTRESSED CONCRETE; PWR TYPE REACTORS; SERVICE LIFE; STRAINS; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; ENRICHED URANIUM REACTORS; LIFETIME; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.